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APPE?idlX B AVERAGE DAILY POWER LEVEL . DOCKET !!O. 060-0325 UNIT BRU'JS?.'ICK UNIT I DATE 06/04/79 CO"PLETED BY EULIS ?'I LLI S TELEPHO!!E 919-457-6711
!.iAY 79
DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY PONER LEVEL (4WE *lET) (MME-r!ET)
i 222. 17 771.
2 0. Id 778.
3 0. 19 542.
4 319. 20 721.
6 621 21 741.
6 746. 22 766 7 790. 23 762.
6 782. 24 784 9 776, 25 642.
10 783. 26 8.
11 778. 27 0,
12 776. 28 q.
13 774 .. 29 0. 14 781. 30 0
15 779. 31 c.
16 701. 2279 127
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I.16 - 8 7906140VLlf ' .
. , , , , OPERATING DATA REPORT Q
00 L , klijf( DOCKET NO. 050-0325 DATE 06/04/79 COMPLETED BY EULIS >!!LLI5 TELEPHOME 919-457-67^1
OPERATING STATUS
1. UNIT NAME: BRUNSWICK UNIT I I NOTES 2. REPORTING PERIOD: MAY 79 I 3. LICENSED THERMAL POMER (MLTT): 2436~ I 4 NAMEPLATE RATING (GROSS M'E): 867.0 I 5. DESIG'l ELECTRICAL RATING (NET MWE): 621.0 I 6. MAX DEPENDABLE. CAPACITY (GRUSS MNE): 315.0 I 7. MAX DEPENDABLE CAPACITY (NET MWE): 790.0 ------d. IF CHAN3ES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPO7T, GIVE RdASONS:
9. POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE): NONE 10. REASONS FOR RESTRICTION IF ANY:
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THIS YR TO CU!UL MONTH DATE ATIVE 11. HOURS IN REPORTING PERIOD 744.0 3523.0 19327.0 12. NUMBER OF HOURS REACTOR '/ AS CRITICAL 563.3 1223.8 13535.4 13. REACTOR RESERVE SHUT 00M!! HOURS 0.0 0.0 1647.1 14. HOURS GENERATOR ON LINE 535.5 110?.9 12552.7 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 16. GROSS THERMAL ENERGY GENERATED (M'.H) 1190845.2 2?99699.5 262:$c90.6 17. UROSS ELECTRICAL ENERGY GENERATED (M'S)/ 401376.0 774423.0 8705730.0 id. NET ELECTRICI AL ENERGY GENERATED (MWH) 386334.0 739314.0 8377912.0 19. UNIT SERVICE FACTOR 72.0 30.4 55.5 20. UNIT AVAILA3ILITY FACTOR. 72.0 3'.4 55.5 21. UNIT CAPACITY FACTOR (USING MDC NET) 65.7 25.8 54.9 22. UNIT CAPACITY FACTOR (USING DER NET) 63.2 24.9 5?.S 23. UNIT FORCED OUTAGE RATE 11.2 9.7 22.5 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
Snubber Inspection 790724 96 Hours 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START UP: 5/ 7/79 26. UNI fS IN TEST STATUS (PRIOR TO COMMERICIAL OPERATION): FORCAST ACHEIVED
INITIAL CRITICALITY ------
INITI AL ELECTRICITY ------
COMMERICIAL OPERATION ------
. 1.16 - 9 J ' 2279 128 -~~ . p ,
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050-0325 UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. UNIT NAM E Brunswick No. 1 DATE June 1979 MAY 1979 COMPLETED BY Eulis A. Wil?is & REPORT MONTil TELEPHONE (919)457-6701_ N -
CN ":- N :, .$ ? 3 )if Licensee 5 r, h. Cause & Corrective No. Date g j= @ jg5 Event g? o1 Action to. H jE $ jgg Report ** in U U Prevent Recurrence 6
007 790501 F 67.4 A 3 N/A CB INSTRU Reactor scrammed on an indicated ADRM upscale thermal trip. The. thermal trip signal was initiated by flow com- parator problems. The flow compara- tor problems were due to vetting of recirculating flow transmitters in the north core spray room. Water entered the room through a sump pump discharge line open check valve from a radwas'te. tanic. Water was being discharged from the room through a temporary hookup . through the Service Water System due to high salt water content when the back- . flow occurred through the installed - sump pump line. The normal system could not be used because the Radwaste System is not designed for high con- ductivity salt water. Water in the - - north core spray room was pumped out
i 2 3 4 - F: Forced Reason: Method: Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of DJ:s B Maintenance or Test 2 Manual Scram. Entr> Sheets for Licensee C Rcfuding 3 Automatic Scram. Event Repm (LER) File (NUREG- D Regt:!atory Restriction 4-Other (Explain) 0161) E Operator Training & License Examination . 5 ' F Administrative G. Operational Error (Explain) Exhibit I Same Sot:rce (9/77) Il Other (Explain) .
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DOCKET NO. 050-0325 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NANIE Brunswick No. 1 DATE June 1979 PfAY 1979 COMPLETED BY Fulis A. Willisc- > REPORT MONT!! TELEP!IONE _ (919)457-6701 m -
Os ";- - N , jg Licensee Cause & Currective , 3 f Ek ,E w, h. No. Date g 3g i jE Event p Action to. H Q y5 $ jgg Report a mo g Prevent Recurrence . c5
. 007 with a temporary pump. Switches that (Cont'd) were wet were replaced or dried out and returned to service. The check valve will be repaired. The long terrn corrective action will be to complete a submitted EWR (#79-37) for storar.e of high conductivity water that rad- waste cannot process. This will allow high conductivity water to be pumped - ~ to storage immediately and processed - or released after sampling.
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- I 2 3 4 - F: Forced Reason: Method: Exhibit G. instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data . B Maintenance of Test 2-Manual Scram. Entr> Sheets for Licensee C Refucting 3 Automatic Scram. Eveni Report (LERI File (NUREG- D. Regulatory Restrictiva 4-Other (Explain) 0161) E-Operator Training & License Examination . F Administrative 5 " G Operational Error (Explain) Exhibis I Same Sourec (9/77) Il-Other (Explain) ,
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050-0325 UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO. a UNIT NAM E Brunswick No. 1 DATE June 1979
COMPLETED BY Eulis A. _ Wfilis REPORT MONTl! MAY 1979 TELEP!!ONE (919)457-6701 - m -
. ":. Ch :, .5 E 3 )Yh Licensee h h. Cause & Corrective No. Date g 3= j .3 g & Event p Action to. g H po 5 5 ig g . Report # mV o Prevent Recurrence . $5 <- 5 u O
* 008 790516 F 8.6 B 1 N/A HC HTEXCH Power was reduced to remove 'A' north waterbox due to conductivity problems. lA north condenser waterbok was. enter- ed and one tube leak was found. Both ends of the tube were plugged. All tubes were checked for protrusions or looseness in the tube sheet. The waterbox was returned to service with no further leakage. - ' .
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I 2 3 4 F: Forced Reason: Method: Exhibit G. Instructions S: Schedu!ed A Equipment Failure (Explain) l-Manual for Preparation of Data . B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LER) File (NUREG- 4-Other (Explain) 0161) D Regulatory Restriction * E Operator Training & License Examination .
F-Administrative 5 ~ ' G Operational Error (Explain) Exhibit 1 Same Sourec (9/77) II Other (Explain)
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DOCKET NO. 050-0175 UNIT SilU'IDOWNS ANI)I'OWER REDUCl!ONS UNIT NAME Bronwlek Nn. 1 DATE June 1979 g COMPLETED BY Eulis A. Willis m REPORT MONTil MAY 1979 TELEP!IONE (919)457-6701 _ , os * N "L N :, .{g 3 )ih Licensee ,E-r, h. Cause & Corrective D No. Date g Eg ( .3 s s Event gg gO3 Action to. I- f5 s j ;f, g Repor a mo g Prevent Recurrence 6
. 010 7905020 S 2.1 H 1 N/A RB CONROD Reduced reactor power for a rod sequence change. This power reduction . is part of a General Electric recom- mended fuel preconditioning procedure for beginning of cycle startups. No corrective actions required.*
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- I 2 3 4 F: Forced Reason: Method: Exhibit G - Insti ictions S: Scheduled A lhguipment Failure (Explain) | Manual for Preparation of Data . B Maintenance of Test 2 Manual Scram. Entr> Sheets for Licensee C Refueling 3. Automatic Scram. Event Repor (LER) File (NUREG. D Regulatory Restriction 4-Other ( Explain) 0161) E. Operator Training & License Examination . 5 ' F Administrative * G. Operational Error (Explain) Exhibit I - Same Source (9/77) Il Other (Explain) .
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UNIT SliUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0325 UNIT NAME Brunswick No. 1 DATE Jime 1979 COMPLETED BY Eulis A. Willis M REPORT MONTil l'AY 1979 TELEPilONE (919)457-6701 m -
Os
. ":. N c es I tra E 6u N , .E _e s , .E ;i Licensee gg gt Cause & Corrective N, No. Date ;- 3g g ,,g g $ Event py o. 3 Action to H 5 Report 4 SU hO Prevent Recurrence $5 <-,5dj=g u O
011 790521 F 6.2 H 1 N/A HF PUMPXX Reduced reactor power to approximatel: ' 67% to secure 1C circulating water * - pump and wash screen. Heavy fish loads caused the IC traveling screen to load up and block circulating flow The traveling screen was started and washed after securing the circulating water pump. Following washing, the circulating water pump was restarted. The screen uash frequency has been changed from every four hours to
. every two hours during heavy fish runs. .
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I 2 3 4 F: Forced Reason: Method: Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entr> Sheets for Licensee C Refucting 3 Automatic Seram. Event Report (LERI File (NUREG. D Regulatory Restrietiun 4 Other (Explain) 0161) E-Operator Training & License Examination F Administrative 5 - G-Operational Error (Explain) Exhibit 1. Same Source (o!77) Il Other (Explain)
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APPENDIX
DOCKET NO. 050-0325 UNIT Brunswick No. 1 DATE June 1979 COMPLETED BY Eulis A. Willis
OPERATIONS SUMMARY
BRUNSWICK NO. 1
Brunswick Unit No. 1 operated at a 65.7% capacity factor for the month of May. The following power changes and shutdowns occurred during the month: May 1 Reactor scram due to wetting of recirculating flow transmitters.
- May 16 Power reduction due to conductivity problems. May 19 Power reduction because of condenser waterbox leak. May 20 Power reduction for a fuel preconditioning procedure. May 21 Power reduction to wash circulating water screen. May 25 Separated from grid for pipe support inspections and modifications. For more information on individual outages, see the Unit Shutdown and Power Reduction Log for the month of May.
Availability factor for the month was 72.0%. The unit is ecpected to return to service June 7, 1979.
There are 154 PWR spent fuel assemblies and 320 BWR spent fuel assemblies stored in the BSEP 1 spent fuel pool.
2279 134
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,iPPErioIX B AVERAGE DAILY PO ER LEVEL DOCKET ?!O. 060-0324 U'ilT iiRUlis'/'ICX UNIT ? DATE 06/04/79 C0!!PLETED BY EULI3 "!ILLI3 TELEPHONE 919-457-6701 |.iAY 79
UAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (|.iWE-NET) (M i'IE-NET)
1 0. 17 0
2 0. Id O.
3 0. 19 54
4 0. 20 186.
5 O. 21 143.
6 0. 22 31.
7 0. 23 115.
8 0 24 380
9 0. 25 299 10 0 26 0
11 0. 27 0
12 0. 28 0
13 0. 29 0. 14 0. 30 0.
IS 0 31 0
16 0.
. 2279 135
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1.16 - 8 . OPERATING DATA REPORT DOCKET NO. 150-0324 DATE 06/04/79 COMPLETED Pi EULIS '1ILLI9 TELEPHO'!E 919-457-6701 OPERATING STATUS
1. UNIf NAME: BRUT!SWICK UNIT 2 I NOTES 2. REPORTING PERIOD: MAY 79 I 3. LICENSEU THERMAL PO'/ER (flNT): 2436 I 4. !!AMEPLATE RATIt!G (GROSS MME): 667.0 I 5. DESIGN ELECTRICAL RATI*lG (NET M'VE): 821.0 I 6. MAX DEPENDABLE CAPACITY (GROSS MWE): '315.0 I 7. MAX DEPENDABLE CAPACITY (NET 9WE): 790.0 ------8. IF CHA.'!GES OCCUR IN CAPACITY RATI.4GS (ITEMS 3 THRU 7) SINCE LAST REP 09T, GIVE RdAS0!!S:
9. POP;ER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE): N0!!E 10. REASO:IS FOR RESTRICTION IF ANY:
THIS Yo TO CU1UL MO.'lTH DATE ATIVE
11. HOURS 1N REPORTING PERIOD 744.0 3623.0 3134d.O- 12. NUMBER OF HOURS REACTOR NAS CRITICAL 226.5 1659.2 20958.e 13. REACTOR RESERVE SHUT 00MN HOURS 0.0 0.0 0.0 14. HOURS GENERATOR ON LINE 109.3 1551.8 19639.; 15. UNIT RESERVE SHUTDONN HOURS 0.0 0.0 0.0 16. GROSS THERMAL ENERGY GENERATED (MWH) 96855.9 2951563.7 3539939d.G 17. GROSS ELECTRICAL ENERGY GENERATED (:RH) 314tl.0 1003456.0 11a19763.0 id. NET ELECTRICIAL ENERGY GENERATED (MWH) 23373.0 959434.0 11347646.0 19. UNIT SERVICE FACTOR 14.7 42.8 62.c 20. UNIT AVAILABILITY FACTOR 14.7 42.8 62.6 21. UNIT CAPACITY FACTOR (USING MDC NET) 4.0 33.5 45.6 22. UNIT CAPACITY FACTOR (USING DER '!ET) 3.8 32.3 44.1 23. UNIT FORCED OUTAGE RATE 29.4 4.1 14.3 24. SHUTDONNS SCHEDULED OVER NEXT 6 M3NTHS (TYPE, DATF. AND DURATION OF EACH):
Snubber Inspection 790701 96 Hours 25. IF SHUTDOV!N AT END OF REPORT PERIOD, ESTIMATED DATE OF START UP: 6/ 9/79 26. UNITS IN TEST STATUS (PRIOR TO COMMERICIAL OPERATION): FORCAST ACHEIVED
INITIAL CRITICALITY ------
INITIAL ELECTRICITY ------
COMMERICIAL OPERATION ------i,,6 _ , 2279 136 J - '
UNITSifUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0324 UNIT NA5tE Brunswick No. 2 DATE June 1979 CO3fPLETED gy Eulis A. Willis - REPORT MONT11 MAY 1979 TELEPIlONE (919)457-6701 Os t% N . ":- - N
-, .3 ? 3 .E Licensee ,E r, , Cause & Corrective * * Nu. Date g 5g 5 .5 s 5 Event Action to I- FJ yE e j gg g Repor: # mo gQ Prevent Recurrence 6
. 005 790312 S C 2 N/A ZZ ZZZZZZ Unit was separated from the grid for - . , a planned refueling / maintenance outage. The unit was synchronized to the grid 78 days after shutdown. - The tinit was scheduled for a 64-day outage. The main contributors to the 14 day delay were: (1) material and equipment problems during core
. spray piping replacement; (2) control rod drive and nuclear instrumentation repairs following control rod drive * maintenance; and (3) repair of . hydrogen seals on generator / condenser. - Problems experienced during core spray replacement occurred during a single job not planned to be repeated - in f'uture outages. No further corrective action required. Better .
' I 2 - 3 4 F: Forced Reason: Method: Exhibit G. instructions S: Scheduled A Equipment Failure (Explaili) 1-Manual for Preparation of Data
B Maintenance or Test . . 2 Manual Scram. Entr> Sheets for Licensee '. C Refucting 3 Automstic Scrain. Event Report (LER) File (NUREG. D Regulatory Restriction 4-Other (Explain) 0161) E Operator Training & License Examination F Administrative 5 G Operational Error (Explain) - Exhibis I . Same Sourec (9/77) Il Other (Explain)
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050-0324 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. UNIT NA3f E Brunswick No. 2 DATE June 1979 FfAY 1979 COMPLETED !!Y Euli Crs . ":- - N - , .!E 3 ).5' Licensee ,Evo h*o Cause & Corrective No. Date i 3g j .i 5 $ Event g g. Action to 6- f5 c2 j di Report # mO g] Prevent itecurrence o * 005 training and supervision will be (Cont 'c ) * given technicians performing control * . . rod drive maintenance in the future. Stock levels for generator parts are being reviewed and increased as required to prevent delays experienced in working existing parts. . . . . . * . . . . ' I 2 - 3 4 F: Forced Reason: - Method: Exhibit G. Instructions S: Scheduled A !L iuipment Failure (Explain) 1. Manual for Preparation of Data D. Maintenance of Test . 2 Manual Scram. Entry Sheets for Licensee . C Refueling 3 Automstic Scram. Event Report (LERI File (NUREG. D-11egularory Restriction 4-Other (Explain) 016I1 - E Operator Training & License Examination F Administrative 5 G Operational Error (Explain) - Exhibit ! Same Souree (9/77) II O:hcr (Explain) * . . ,. , 050-0324 UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. UNIT NAM E Brunswick No. 2 DATE June 19 79 COMPLETED BY Eulis A. Willis & REPORT MONTil MAY 1979 TELEP!IONE (919)457-6701 m - & w. ~ t% c ci w 5 5 N , ,a _e s '.33 .s x L.icensee g -r, gn, Cause & Currective Ne No. Date i 5g s jgu Event gy c. Action to 8- y5 5 3 ;:j ;: Report # wU O Prevent Recurrence a s u!] O * 006 790519 S 1.2 H 1 N/A ED TURBIN Removed unit from grid for a turbine , overspeed trip test. Required after * . . extensive maintenance on the turbine and annual preventative maintenance , was due. . . . . . . . . ' I 2 - 3 4 F: Forced Reason: Method: Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data . . D-Maintenance of Test . 2-Manual Scram. Entr> Sheets far Licensee . C-Refueling 3 Automatic Scram. Event Repuri (LER) File (NUREG- D Regularory Restriction 4-Other (Explain) 01611 E Operator Training & License Examination F Administrative 5 G Operational Error (Explain) - Exhibit I Same Source (of77) !! Other (Explain) , % UNIT SlfUTDOWNS AND POWER REDUCTIONS . DOCKET NO. 050-0324 UNIT NAME Brunswfek No. 2 DATE J""e 1979 COMPLETED BY Eulis A. Willis REPORT MONTil MAY 1979 CD TELEPl!ONE (919)457-6701 w - . Os , .E g 3 Y Licensee ,E-r, o Cause & Corrective N * No. Date g g @ .5 g s Event gg gu3 Action to N H gE e j Report mu o Prevent Recurrence 3e - ;g: o O . . 007 790521 F 31.7 B 3 N/A IA INSTRU Reactor scram--cause(s) unkno ,- The , , exact parameter which causert the scram - - is unknown. The computer printout which furnishes this information was inoperable and the recorders or indi- cators on the control board indicated no abhormal transients at the time of the scram. A surveillance test on reactor vessel water level instruments - was in progress and the reactor scram occurred simultaneously with opening - an instrument isolation valve. The computer printout for the cause of the' ' scram was made operable. The surveil- * 1ance test was completed. What effects - the opening of the instrument valve would have on other instruments which share the same instrument piping lines - was analyzed. At operating pressure, ' t 2 - 3 4 - F: Forced Reason: Method: Exhibit G Instructions S: Scheduled A 1:stuipment Failure (Explain) 1 Manual for Preparation of Daia D Maintenance of Test . 2 Manual Serarn. Entr> Sheets for Liecusee . C Refucting 3 Automatic Scram. Event Report (LERI Fife (NUREG- D Regulatory Restriction 4-Other (Explain) 0161) - E Operator Training & License Examination F Administrative 5 G. Operational Error (Explain) - Exhibit I Same Sourec (9/77) Il Other (Explain) - . - . . UNIT SilUIDOWNS AND POWIER REDUCTIONS DOCKET NO. 050-0324 UNIT NAME 11runswick No. 2 DATE June 1979 _ COMPLETED I!Y Eulis A. Willis y REPORT MONTir MAY 1979 TELEP!!ONE (919)457-6701 - Os ' fN . ":- N - , .! ? 3 ) .E Licensee ,E s he. Cause & Currective D No. DJte g 3g ( jg5 Event =7 Action to H c-] $5 $ 3g= Report # SU $ Preve:!! Recurrence e g u o - . 007 the opening of this valve could cause (Cont't) , a false pressure transient .to be * - sensed and cause the scram. The reac- - tor was restarted. A plant modifica- - tion-will be installed to place sensitive instruments on separated reference legs which should reduce the possibility of this type of scram. This modification will be installed in - both units during the 1980 refueling outages. . . . . - . . . ' I 2 - 3 4 F: Forced Reason: Method: Exhibit G. Instructions S: Scheduled A Eiguipment Failure (Explain) 1 Manual for Preparation of Data 11. Maintenance of Test , 2 M inual Sctsm. Entr> Sheeis for Licensee . C Refeeling 3-Automatic Scram. Event Report (LER) Fife (NUREG- D Ret :!atory Restriction 4 Other(Explain) 0161) E Operator Training & License Examination F Administrative . 5 G Operational Error (Explain) - Exhibit I-Same Sourec (9/77) Il Other (Explain) . . . . ~ % 050-0324 UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. UNIT NAME _ Brunswiek No. 2 DATE June 1979 COMPLETED BY Eulis A. Willis N REPORT MONT!! MAY 197Q TELEPilONE (919)(357-6701 , - ~. Ch - E E N ;, .$E 3 $ Yit Liecusee 5-r, E*., Cause & Cuirective CN No. Date 3 gg y jg$ Event ay E1 Action to N H g3 E E Report # NU hO Prevent Recurrence 5e. 5 :! u c5 . 008 790523 F 13.9 C 3 Cll PUMPXX ' N/A Reactor scrammed on low water level. 2A reactor feed pump on-line in pre- prcation of testing 2B reactor feed pump. Operator was to reset the 2B reactor feed pump motor speed changer to minimum. By mistake he got oa the - - 2A reactor feed pump centrols and ran that pump back to minimum causing a low reactor water level. A reactor scram occurred, 2A and 2B reactor , recirculation pumps tripped, and main steam isolation valves (MSIV) closed. Followed Emergency Instruction for - reactor scram, opened MSIV and re- started the reactor recirculation pumps. Performed a reactor startup. The' operator was counseled on the ne- cessity of thinking through an evolu- , tion orior to startine it and then i 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A Equipment Failure (Exp!ain) 1 -Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Er.tr> Sheets for 1.ieensee C Refucting 3-Automatic Scram. Event Repor (LER) FdeINUREG- D Regu|atory Restriction 4-Other (Explain) 0161) E-Operator Training & License Examination F Administrative 5 G Operational Error (Explain) Exhibit I Same Source (9/77) II-Other (Explain) , . e . ~. s UNITSifUTDOWN5 AND POWER REDUCTlONS DOCKET NO. 050-0324 UNIT NA31E Brunswick No. 2 re DATE June 1979 e ' REPORTMONTil _ MAY 1979 COMPLETED BY Enlia 4 Wf114= - TELEPlf0NE (919)457-6701 Os N N . ":- -- N -, .! ? 3 .E Licensee ,Eg E% Cause & Corrective - . No. Date B, 5g s .5 i E Event g? c-3 Action to l- f5 5 Report # wO 5O 34 ;g =g u Prevent Recurrence o 008 . * paying close attention to what'he was (Cont'd) - , doing. The reactor feed pump controls were conspiciously labeled. A letter * was issued by the Plant Manager to the Plant Management Group concerning per- sonnel errors and the serious conse- quences of them. A review meeting was held with those involved in this outage , to review the event and determine means to prevent future outages of this type. . - . . . ' I 2 - 3 4 F: Forced Reason: Method: S: Scheduled A.!:ituipment Failure (Explain) Exhibit G-Instructions 1 -Manual for Preparation of Dara , D-Maintenance of Test , 2 Manual Scrsm. C-Refuctin; Entr) Sheets for Licensee 3-Automatic Scram. Event Repor (LERI File (NUREG- D Regulatory Restriction 4-Other (Explain) E-operator Training & License Examination 01611 F Administrative 5 G Operational Error (Explain) - (4/77) Il Other (Explain) Exhibit I Same Source , . e * , APPENDIX DOCKET No. 050-0324 UNIT Brunswick No. 2 DATE June 1979 COMPLETED BY Eulis A. Willis OPEPATIONS SUMMARY BRUNSWICK NO. 2 Brunswick Unit No. 2 synchronized to the grid May 19, 1979, at 0715, completing an approximately 1854 hour refueling outage. The unit was either forced or man- ually separated from the grid four other times during the month, resulting in a ,14.7% availability factor. The unit capacity factor was 4% for the month of May. A detailed description of the refueling outage and other outages is pro- vided in t.he Unit Shutdown and Power Reductions Log (Appendix D) provided with this report. The unit is shut down at the end of the report period for pipe support inspec- tions and modifications, and is expected back "on-line" June 9, 1979. There are 28 PWR spent fuel assemblies and 132 BWR spent fuel assembiles stored in the BSEP 2 spent fuel pool. 2279 144 .